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Plutonium
Disposition
One of
the most difficult materials to properly disposition following
the dimantlement of nuclear weapons is plutonium. The final dispositioned
form must not only provide adequate immobilization but also make
theft very difficult.
Mixed
Oxide (MOX) Fuel
One method of plutonium disposition is to combine plutonium oxide
with uranium oxide as a nuclear reactor fuel. Following power
generation the spent MOX fuel serves as a temporary immobilized
form and the fission products are highly radioactive making theft
more difficult.
Reports:
•
Mechanisms of Thermal Induced Gallium Removal (TIGR)
from Plutonium Dioxide
Scott F. DeMuth
LA-UR-98-6566 (August 1998)
Download
pdf (282 KB)
•
Technical Report for Generic Site Add-On Facility for
Plutonium Polishing
Scott F. DeMuth, et. al.
ORNL/TM-13662 (June 1998)
Download pdf (183 KB)
•
Preconceptual Design for Separation of Plutonium and
Gallium by Ion Exchange
Scott F. DeMuth
LA-UR-97-3769 (September 1997)
Download
pdf (233 KB)
•
Conceptual Design for Separation of Plutonium and Gallium
by Solvent Extraction
Scott F. DeMuth
LA-UR-97-181 (April 1997)
Download
pdf (125 KB)
•
Response to the Surplus Plutonium Disposition Environmental
Impact Statement (EIS) Data Call for a Mixed Oxide Fuel Fabrication
Facility Located at the Hanford Site
Scott F. DeMuth, et. al.
LA-UR-97-2064 (1997)
Download pdf (13
MB)
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Response to the Surplus Plutonium Disposition Environmental
Impact Statement (EIS) Data Call for a Mixed Oxide Fuel Fabrication
Facility Located at the Idaho Falls Engineering and Environmental
Laboratory
Scott F. DeMuth, et. al.
LA-UR-97-2065 (1997)
Download pdf (10
MB)
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Response to the Surplus Plutonium Disposition Environmental
Impact Statement (EIS) Data Call for a Mixed Oxide Fuel Fabrication
Facility Located at the Pantex Plant
Scott F. DeMuth, et. al.
LA-UR-97-2067 (1997)
Download pdf (10
MB)
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Response to the Surplus Plutonium Disposition Environmental
Impact Statement (EIS) Data Call for a Mixed Oxide Fuel Fabrication
Facility Located at the Savannah River Site
Scott F. DeMuth, et. al.
LA-UR-97-2066 (1997)
Download pdf (10
MB)
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